CN115295179A - Compensation method for reactor power measurement - Google Patents
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Abstract
The embodiment of the invention discloses a compensation method for reactor power measurement. The reactor core periphery of the reactor is provided with a movable reflecting layer, the reactivity of the reactor is controlled through the displacement of the reflecting layer, and a plurality of nuclear detectors are arranged outside the reflecting layer. The compensation method is used for compensating the deviation of the displacement of the reflecting layer to the power measurement value of the reactor and comprises the following steps: obtaining power measurement values of a working group detector and a compensation group detector in the plurality of nuclear detectors; determining the position of the reflecting layer according to the ratio of the power measurement values of the working group detector and the compensation group detector; determining a power compensation coefficient of the working group detector according to the position of the reflecting layer; and compensating the power measurement value of the working group detector by using the power compensation coefficient to obtain the current power value of the reactor.
Description
Technical Field
The embodiment of the invention relates to the technical field, in particular to a compensation method for reactor power measurement.
Background
In a reactor, a reflective layer can be used to control the reactivity of the reactor, which requires control of the reactivity by shifting the degree to which it shields the core. However, when the reflecting layer moves up and down, the neutron fluence rate level and distribution in space both change drastically, and the change law of the neutron fluence rate at different positions has a significant difference.
The power of the reactor is typically measured using a nuclear detector that indirectly measures the reactor power by measuring the neutron fluence rate of the reactor. For a specific reactor with reactivity controlled by the reflecting layer, the nuclear detector is arranged outside the reflecting layer, and the displacement of the reflecting layer can obviously influence the measurement result of the nuclear detector on the reactor power, so that the power value measured by the nuclear detector deviates from the real reactor power.
Disclosure of Invention
According to one aspect of the invention, a method of compensating for reactor power measurements is provided. The reactor core periphery of the reactor is provided with a movable reflecting layer, a plurality of nuclear detectors are arranged outside the reflecting layer, and the reactivity of the reactor is controlled through the displacement of the reflecting layer. The compensation method is used for compensating the deviation of the displacement of the reflecting layer on the measured value of the power of the reactor and comprises the following steps: obtaining power measurement values of a working group detector and a compensation group detector in the plurality of nuclear detectors; determining the position of a reflecting layer according to the ratio of the power measurement values of the working group detector and the compensation group detector; determining a power compensation coefficient of the working group detector according to the position of the reflecting layer; and compensating the power measurement value of the working group detector by using the power compensation coefficient to obtain the current power value of the reactor.
Drawings
Other objects and advantages of the present invention will become apparent from the following description of the embodiments of the present invention with reference to the accompanying drawings, and may help to provide a full understanding of the present invention.
Fig. 1 is a schematic view of the structure of a reactor according to an embodiment of the present invention.
Fig. 2 is a schematic view of the radial structure of the reactor of fig. 1.
Fig. 3 is a schematic axial configuration of the reactor of fig. 1.
FIG. 4 is a schematic illustration of the movement of a reflective layer to different positions in a reactor according to one embodiment of the present invention.
FIG. 5 is a flow diagram illustrating a compensation method according to an embodiment of the invention.
Fig. 6 is a flow chart illustrating a compensation method according to another embodiment of the present invention.
Fig. 7a and 7b are schematic diagrams of a variation of neutron fluence rate at a plurality of detector positions according to an embodiment of the invention.
Fig. 8 is a schematic diagram of the function f1 determined from the variation graph G (x) in fig. 7 b.
Fig. 9 is a schematic diagram of the function f2 determined from the variation graph G (x) in fig. 7 b.
It is noted that the drawings are not necessarily to scale and are merely illustrative in nature and not intended to obscure the reader.
Description of reference numerals:
10. a core; 20. a reflective layer; 1-6, nuclear detector.
Detailed Description
In order to make the objects, technical solutions and advantages of the present application more clear, the technical solutions of the present application will be described below in detail and completely with reference to the accompanying drawings of the embodiments of the present application. It should be apparent that the described embodiment is one embodiment of the present application and not all embodiments. All other embodiments, which can be derived by a person skilled in the art from the described embodiments of the application without any inventive step, are within the scope of protection of the application.
It is to be noted that, unless otherwise defined, technical or scientific terms used herein shall have the ordinary meaning as understood by those of ordinary skill in the art to which this application belongs. If the description "first", "second", etc. is referred to throughout, the description of "first", "second", etc. is used only for distinguishing similar objects, and is not to be construed as indicating or implying a relative importance, order or number of technical features indicated, it being understood that the data described in "first", "second", etc. may be interchanged where appropriate. If "and/or" is presented throughout, it is meant to include three juxtapositions, exemplified by "A and/or B" and including either solution A, or solution B, or both solutions A and B. Furthermore, spatially relative terms, such as "above," "below," "top," "bottom," and the like, may be used herein for ease of description to describe one element or feature's spatial relationship to another element or feature as illustrated in the figures, and should be understood to encompass different orientations in use or operation in addition to the orientation depicted in the figures.
Fig. 1 shows a schematic structural view of a reactor according to an embodiment of the present invention. Fig. 2 and 3 show schematic diagrams of the reactor of fig. 1 from different perspectives.
Referring to fig. 1 to 3, a reactor includes a core 10, a reflective layer 20, and a plurality of nuclear detectors. The movable reflective layer 20 is disposed at the periphery of the core 10 and is adjacent to the core 10, and the plurality of nuclear detectors are disposed outside the reflective layer 20 and distributed at different positions around the reflective layer 20. The nuclear detectors 1 to 4 are uniformly arranged along the circumferential direction of the reflective layer 20, the nuclear detector 5 is arranged above the reactor core 10, and the nuclear detector 6 is arranged below the reactor core 10.
Fig. 4 shows a schematic view of a displacement of a reflective layer to a different position according to an embodiment of the invention. The reflective layer 20 may be displaced up and down within a range as shown in fig. 4, that is, within a range from when the reflective layer 20 is completely separated from the core 10 to when the reflective layer 20 completely blocks the core 10, so that the reactivity of the reactor is controlled by the displacement of the reflective layer 20.
When the reflecting layer 20 moves to different positions, the size and distribution of the neutron fluence rate in the surrounding space can be changed significantly, and the position of the reflecting layer 20 has different influence relationships on the neutron fluence rate at different positions. Therefore, even under the condition that the actual power level of the reactor is not changed due to the influence caused by the displacement of the position of the reflecting layer 20, the reactor power values measured by the nuclear detectors (1-6) at different positions are changed, so that the reactor power directly measured by the nuclear detectors (1-6) is obviously deviated due to the controllable displacement of the reflecting layer 20.
The embodiment of the invention provides a compensation method for reactor power measurement, which can be used for compensating the deviation of the displacement of a reflecting layer on the reactor power measurement value to obtain a relatively real reactor power value. Fig. 5 shows a schematic flow diagram of a compensation method according to an embodiment of the invention. As shown in fig. 5, the compensation method in this embodiment specifically includes the following steps.
And S11, acquiring power measurement values of a working group detector and a compensation group detector in a plurality of nuclear detectors in the reactor.
S12, determining the position of a reflecting layer according to the ratio of the power measurement values of the working group detector and the compensation group detector; and determining the power compensation coefficient of the working group detector according to the position of the reflecting layer.
And S13, compensating the power measurement value of the working group detector by using the power compensation coefficient to obtain the current power value of the reactor.
Compared with the obvious deviation caused by the influence of the controlled displacement of the reflecting layer on the reactor power value directly measured by the nuclear detector, the compensation method provided by the embodiment of the invention utilizes the power measurement values of the working group detector and the compensation group detector to obtain the power compensation coefficient through calculation, can be used for compensating the influence of the controlled displacement of the reflecting layer on the reactor power measurement result, and improves the measurement precision of the nuclear detector for measuring the reactor power.
In step S11, the output signals of the working group detector and the compensation group detector may be received and processed to obtain the power measurement value of the working group detector and the power measurement value of the compensation group detector.
In step S12, the power measurement of the active set detector and the power measurement of the compensation set detector are first scaled. Specifically, the ratio of the two may be numerically the workgroup detector power measurement (P) a ) Divided by the compensated set of detector power measurements (P) b ) I.e. P a /P b (ii) a Alternatively, it may be a compensated group detector power measurement (P) b ) Divided by the workgroup detector power measurement (P) a ) I.e. P b /P a (ii) a Alternatively, it may be a workgroup detector power measurement (P) a ) And the measured value of the detector power (P) of the compensation group b ) Difference after logarithmic operation, i.e. | log z P a -log z P b Where z is an arbitrary base number.
After the ratio between the power measurement value of the working group detector and the power measurement value of the compensation group detector is obtained through calculation, the position of the reflecting layer can be determined through a specific algorithm according to the ratio, and the power compensation coefficient of the working group detector can be determined through the specific algorithm according to the position of the reflecting layer.
In step S13, the power measurement (P) of the workgroup detector is compensated using the calculated power compensation factor a ) Specifically, the current power value of the reactor can be obtained by multiplying the power measurement value of the working group detector by the power compensation coefficient. In this embodiment, the power value compensated by the power compensation coefficient is close to the real power of the reactor, and the deviation between the power value compensated by the power compensation coefficient and the real power of the reactor is small, so that the measurement accuracy of the nuclear detector in measuring the power of the reactor is improved.
In some implementations, it is first necessary to select the locations of the workgroup detectors and the compensation group detectors in the reactor. Wherein, the output signal of the working group detector can be used for calculating the final current power value of the reactor, and the output signals of the working group detector and the compensation group detector are jointly used for determining the power compensation coefficient.
Optionally, the number of the working group detectors may be one or more, and the number of the compensation group detectors may also be one or more. The plurality of working group detectors can share one compensation group detector, and each working group detector can be correspondingly provided with one compensation group detector.
In some embodiments, the positions of the active set of detectors and the compensation set of detectors may be selected based on the neutron fluence rate at each nuclear detector position in the reactor as a function of the position of the reflector at a constant reactor power. When the reactor power is constant, for example, at a certain constant reactor power, the variation relationship of the neutron fluence rate at each nuclear detector position with the position of the reflecting layer can be recorded as a function G (x), the independent variable of G (x) is the position of the reflecting layer, and the function value is the neutron fluence rate at the nuclear detector position. In this embodiment, the positions of the active set detectors and the compensation set detectors may be selected according to the function G (x) of each nuclear detector.
It should be noted that the nuclear detector indirectly measures the reactor power by measuring the neutron fluence rate, and the neutron fluence rate level at the position of the nuclear detector corresponds to the measured value of the reactor power measured by the neutron fluence rate level. Therefore, the function G (x) of the variation relationship of the neutron fluence rate at each nuclear detector position with the position of the reflecting layer when the acquired reactor power is constant can also reflect the variation relationship of the measured value of the reactor power measured by each nuclear detector with the position of the reflecting layer.
Specifically, the following conditions need to be satisfied when selecting the positions of the working set of detectors and the compensation set of detectors: when the reactor power is constant, the range of variation of the function value of G (x) at the position of the workgroup detector is smaller than that of G (x) at the position of the compensation group detector, i.e. the range of variation of the function value of G (x) at the position of the workgroup detector should be as small as possible, and the range of variation of the function value of G (x) at the position of the compensation group detector should be as large as possible. Meanwhile, the neutron fluence rate at the position of the compensation group detector should satisfy a single-valued function relationship along with the change of the reflecting layer, that is, G (x) at the position of the compensation group detector is a single-valued function. Furthermore, the ratio of G (x) at the location of the compensation group detector to G (x) at the location of the active group detector should also be a single valued function.
In this embodiment, the nuclear detector with a smaller function value change range of G (x) is selected as the working group detector, which is less affected by the controllable displacement of the reflective layer, so that the deviation of the power measurement value directly measured by the working group detector is also smaller, and power compensation is performed on the basis, which is beneficial to further improving the precision and obtaining more accurate reactor power.
In addition, in this embodiment, the nuclear detector with the larger function variation range of G (x) is selected as the compensation group detector, so that when the ratio of the power measurement values of the compensation group detector and the working group detector is subsequently calculated, the signal-to-noise ratio of the calculated ratio can be improved, and the signal-to-noise ratio of the ratio is prevented from being poor due to the smaller function value variation ranges of G (x) of the compensation group detector and the working group detector. Meanwhile, G (x) of the compensation group detector selected in this embodiment is a single-valued function, and a ratio of G (x) at the position of the compensation group detector to G (x) at the position of the working group detector should also be a single-valued function, so that it can be avoided that the functions f1 and f2 cannot be obtained by subsequent calculation because G (x) at the position of the detector is a multiple-valued function or a ratio of G (x) at the positions of the working group detector and the compensation group detector is a multiple-valued function.
It should be noted that the "range of variation of the function value of G (x)" described in the embodiment of the present invention refers to a difference between a maximum function value and a minimum function value of the function value of G (x).
In some embodiments, when the reactor core is provided with a plurality of movable reflective layers around its periphery, the position of the workgroup detectors may also need to be selected to take into account the uniformity of the nuclear detectors in direction. Specifically, the position of the working group detector can be selected according to the influence relationship of each reflecting layer on the neutron fluence rate at the position of each nuclear detector, wherein the influence relationship of each reflecting layer on the neutron fluence rate at the position of the working group detector is consistent as much as possible, so that when different reflecting layers respectively displace, the compensation coefficient can be calculated through the same algorithm, the calculated amount can be reduced, the reactor power value close to the actual value can be obtained, and when a plurality of reflecting layers displace together, the accurate compensation coefficient can be stably calculated, and the reactor power value is more accurate.
Likewise, in some embodiments, when the core periphery of the reactor is provided with a plurality of movable reflective layers, the position of the compensation group detectors also needs to be selected to take into account the directional uniformity of the nuclear detectors. Specifically, the position of the compensation group detector can be selected according to the influence relationship of each reflection layer on the neutron fluence rate at each nuclear detector position, wherein the influence relationship of each reflection layer on the neutron fluence rate at the compensation group detector position should be as consistent as possible, so that when different reflection layers respectively displace and a plurality of reflection layers displace together, accurate compensation coefficients can be stably calculated, and further, a relatively accurate reactor power value is obtained.
Taking the reactor shown in fig. 1 to 4 as an example, as shown in fig. 2, 3 movable reflecting layers (reflecting layers 20-1, 20-2, 20-3) are uniformly arranged in the circumferential direction of the core 10 on the periphery of the core 10, 4 nuclear detectors (nuclear detectors 1 to 4) may be arranged in the radial direction of the core 10, and two nuclear detectors (nuclear detectors 5 and 6) may be arranged in the axial direction of the core 10.
Wherein, different reflection layer displacements have different influence relationships on the neutron fluence rate at any one of the nuclear detectors 1 to 4, and the influence relationships on the neutron fluence rate at the nuclear detector 5 or 6 are close to or even consistent. For example, at the position of the nuclear detector 6, the function of the neutron fluence rate as a function of the position of the reflecting layers 20-1, 20-2 is G (x) 1 And G (x) 2 And G (x) 1 And G (x) 2 Very closely or even uniformly. Thus, when selecting the position of the active set detector or the compensation set detector, the position of the nuclear detector 5 or the nuclear detector 6 may be selected.
Further, as shown in fig. 4, when the reactor power is set to the rated power and is not changed, in the process of shifting the reflector 20 from the position completely separated from the core 10 (as shown in fig. 4 a) to the position where the reflector 20 completely blocks the core 10 (as shown in fig. 4 d), the neutron fluence rate change curves (i.e., G (x) function curves) at the positions of the nuclear detectors 1 to 6 are shown in fig. 7a and 7b, where the abscissa represents the reflector position, i.e., the proportion of the portion of the core blocked by the reflector, for example, the abscissa corresponding to the reflector 20 completely separated from the core 10 is 0%, the abscissa corresponding to the half of the core 10 blocked by the reflector 20 is 50%, and the abscissa corresponding to the reflector 20 completely blocks the core 10 is 100%.
Referring to fig. 7a and 7b, the range of variation of the G (x) function value at the position of the nuclear detector 6 is smaller than the range of variation of the G (x) function value at the position of the nuclear detector 5, and the G (x) function at the position of the nuclear detector 5 is a single-value function. Thus, the nuclear detector 6 can be selected as the active set detector and the nuclear detector 5 as the compensation set detector.
Furthermore, in some embodiments, when selecting the workgroup detector and the compensation group detector, the compensation group detector and/or the workgroup detector may also be selected based on spatial location in the reactor. Specifically, when the working group detector and/or the compensation group detector are/is arranged, the spatial position where the working group detector and/or the compensation group detector are/is not interfered with the positions of other devices, and the arrangement of the other devices is not influenced.
In the present embodiment, the compensation coefficient may be calculated by using a specific algorithm. After the positions of the working group detector and the compensation group detector are selected, a function G (x) of the relation between the neutron fluence rates at the positions of the working group detector and the compensation group detector and the position change of the reflecting layer when the reactor power is constant can be obtained, and a reflecting layer position relation function f1 and a compensation coefficient relation function f2 are determined through corresponding physical calculation according to the function G (x) at the positions of the working group detector and the compensation group detector.
The function f1 is a numerical relational expression between the ratio of the neutron fluence rates at the positions of the working group detector and the compensation group detector and the position of the reflecting layer, and can describe the relation between the difference change of the neutron fluence rates at the positions of the compensation group detector and the working group detector and the position of the reflecting layer, the independent variable of the function f is the ratio of the power measurement values of the working group detector and the compensation group detector, and the function value of the function f is the position of the reflecting layer.
In particular, the function f1 may be the inverse of the ratio of the G (x) function at the active set detector positions to the G (x) function at the compensation set detector positions. When the reactor power is constant at a certain power value, the function f1 can be obtained by calculating the ratio of the power measurement values of the compensation group and the working group detector when the reflecting layer is at different positions, or the ratio of the neutron fluence rates at the positions of the compensation group and the working group detector, and then calculating through an inverse function.
Taking the reactor shown in fig. 1-4 as an example, when the nuclear detector 6 is selected as the working group detector and the nuclear detector 5 is selected as the compensation group detector, the variation of the neutron fluence rate at the positions of the working group detector and the compensation group detector with the position of the reflecting layer is shown in fig. 7 b. Let the G (x) function at the workgroup probe location be G (x) a Let the G (x) function at the location of the compensating group of detectors be denoted as G (x) b Then function G (x) a /G(x) b I.e. the function f1, the graph of the function f1 is shown in fig. 8.
The function f2 is a numerical relation between the position of the reflecting layer and the power compensation coefficient of the workgroup detector, and can describe the relation between the position of the reflecting layer and the neutron fluence rate at the position of the workgroup detector, the independent variable of the function is the position of the reflecting layer, and the function value is the power compensation coefficient of the workgroup detector.
Specifically, the function f2 is the ratio of the neutron fluence rate at the location where the reflection layer is at the reference point to the G (x) function at the workgroup detector location. After the compensated reference point is selected, the function f2 can be obtained by dividing the neutron fluence rate at the position of the workgroup detector when the reflection layer is at the position of the reference point by the G (x) function at the position of the workgroup detector. At the reference point location, the function f2 outputs a compensation factor of 1, i.e. no compensation of the power measurements of the active set detectors is required.
Taking the reactor shown in fig. 1-4 as an example, when the nuclear detector 6 is selected as the active set detector and the nuclear detector 5 is selected as the compensation set detector, the variation of the neutron fluence rate at the active set detector position with the position of the reflector is shown in fig. 7 b. For example, when a position where the reflective layer 20 completely blocks the core 10 (i.e., a position whose abscissa is 100% in fig. 7 b) is selected as a reference point, the neutron fluence rate G at the position of the workgroup detector is set to be a value 0 Divided by function G (x) at the location of the workgroup detector a I.e. G 0 /G(x) a I.e. function f2, the graph of function f2 is shown in fig. 9.
In this embodiment, a compensated reference point needs to be selected before determining the function f2. The nuclear detector measures the reactor power indirectly by measuring the neutron fluence rate, and different neutron fluence rates at the position of the detector of the working group correspond to different reactor power values. At the position of the workgroup detector, the neutron fluence rate corresponding to the reactor power of 100% is n, and in this embodiment, the position of the reflection layer corresponding to the neutron fluence rate of n at the position of the workgroup detector may be selected as the reference point according to the function G (x) at the position of the workgroup detector. When the reflecting layer is positioned at the reference point, the power measured value of the working group detector is 100%, and when the reflecting layer is positioned at other positions, the power measured value measured by the working group detector can be compensated relative to the 100% power value corresponding to the reference point.
When the functions f1, f2 are determined, the compensation coefficients can be calculated from f1 and f2.
Referring to fig. 6, the compensation method of the present embodiment specifically includes steps S21 to S23. Steps S21 and S23 are the same as steps S11 and S13 in the above embodiments, respectively, and are not described again here.
In step S22, first, the current position of the reflective layer is determined according to the ratio between the power measurement values of the working group detector and the compensation group detector and the function f 1; and determining the power compensation coefficient of the working group detector according to the determined position of the reflecting layer and the function f2. And when the compensation coefficient is obtained through calculation, the power measurement value measured by the working group detector can be compensated, namely, the power measurement value measured by the working group detector is multiplied by the determined power compensation coefficient to obtain the final current power value of the reactor.
When only one reflective layer is disposed in the reactor, or when all reflective layers (reflective layer groups) in the reactor are displaced synchronously, the position of the reflective layer calculated by the function f1 in the embodiment of the present invention may be directly regarded as the position of the reflective layer or the reflective layer group. When the reactor is provided with a plurality of reflecting layers, and only one reflecting layer (called as an adjusting reflecting layer) is displaced under the power operation condition, and other reflecting layers are fixed at the position opposite to the reactor core and are not moved, the position of the reflecting layer obtained through the calculation of the function f1 can be regarded as the position of the adjusting reflecting layer. When a plurality of reflecting layers are arranged in the reactor and all the reflecting layers can be displaced under the power operation condition, the position of the reflecting layer obtained through calculation of the function f1 can be regarded as the average effective position of all the reflecting layers.
In some embodiments, the data processing system may be configured to perform power compensation. Specifically, after the workgroup and compensation group detectors are set, the data processing system may be connected to the workgroup and compensation group detectors to obtain output signals of the workgroup and compensation group detectors. Stored in the data processing system is a computer program which, when executed, causes the data processing system to perform the compensation method in the embodiment shown in fig. 6. When the functions f1 and f2 are determined, the functions f1 and f2 may be input to the data processing system so that the power measurements can be compensated.
Specifically, when the reactor power is measured, the data processing system firstly obtains output signals of the detectors of the working group and the compensation group and converts the output signals into power measurement values, then calculates the ratio of the power measurement values of the detectors of the working group and the compensation group, inputs the ratio into the function f1, enables the function f1 to output the position of the reflecting layer, inputs the position of the reflecting layer into the function f2, enables the function f2 to output a power compensation coefficient, and finally multiplies the power measurement value of the detectors of the working group by the power compensation coefficient, so that the current power value of the reactor is obtained and displayed on a display of the data processing system. In addition, when the reactor power is measured in real time, a curve of the reactor power changing along with time can be obtained.
It should be noted that the function G (x) of the variation of the neutron fluence rate at each nuclear detector position with the position of the reflecting layer is obtained through physical calculation. After the reactor core design and the reflecting layer design of the reactor are finished, the influence relation of the reflecting layer control displacement on the neutron fluence rate in the space can be calculated, namely, the function G (x) of the neutron fluence rate at the position of the detector along with the position change relation of the reflecting layer is calculated. The function G (x) may be calculated by using a physical calculation method in the related art of reactor design, and the specific calculation method is not limited in this embodiment. For example, the function G (x) can be obtained by calculating the neutron fluence rate at each position in space when the reflecting layer is at different positions in the reactor through simulation.
In order to compensate the influence of the displacement of the reflecting layer on the measurement of the mobile power, in the conventional method, the real-time position of the reflecting layer is generally directly measured, and then the value of the reactor power measurement is compensated in a targeted manner according to the displacement of the reflecting layer. The method has the greatest disadvantage that the position measurement of the reflecting layer or the control rod is a non-safety-level measurement parameter in a common nuclear power plant and a nuclear facility, and the reactor power measurement is generally required to be a safety-level measurement parameter. If the scheme of directly measuring the position of the reflecting layer is adopted, the position measurement needs to be promoted from a non-safety level to a safety level, and the measurement precision of the position also needs to be correspondingly promoted, and the existing technical conditions are difficult to meet the requirement.
Compared with the traditional method, the compensation method in the embodiment of the invention does not increase the types of the measurement parameters and does not depend on other measurement systems to work. The measurement parameters used by the compensation method of the embodiment of the invention are the measurement parameters of the nuclear detector, and compared with the measurement method without power compensation, the method only increases the number of the parameters, but does not increase the types of the parameters. Compared with some potential methods which need to utilize other parameters besides the nuclear detector measurement parameters, the method provided by the embodiment of the invention has the advantage that the measurement parameter types are not increased, and the measurement of the reactor power can still be independently completed by a nuclear measurement system.
In addition, the method in the embodiment of the invention does not change the measurement principle of the reactor power. The measurement principle of the detector, whether a working group detector or a compensation group detector, is to convert the electrical parameters output by the nuclear detector into neutron fluence rate and then into reactor power without the help of other measurement principles.
Compared with a method for directly measuring the position of the reflecting layer and then compensating the influence of the displacement of the reflecting layer on the measurement of the power of the reactor, the compensation method in the embodiment of the invention can meet the requirement of the safety level of the power measuring equipment of the reactor.
In addition, the compensation method in the embodiment of the invention can additionally obtain the parameters of the position of the reflecting layer. The position parameters of the reflecting layer in the embodiment of the invention are obtained by indirect calculation of the nuclear detector parameters at different positions, and can be applied to multiple aspects. For example, the position of the reflecting layer obtained by indirect calculation in the embodiment of the present invention and the directly measured position parameter of the reflecting layer are checked with each other, or the moving direction of the reflecting layer is determined according to the change of the position of the reflecting layer, or the burnup depth of the reactor is estimated according to the position of the reflecting layer and other parameters.
According to the compensation method in the embodiment of the invention, the position of the reflecting layer is obtained by utilizing the difference change of the power measurement values of the plurality of nuclear detectors through calculation of the specific algorithm, and the deviation of the power measurement value of the reactor is compensated by utilizing the position of the reflecting layer through the specific algorithm, so that the deviation caused by the controllable displacement of the reflecting layer during the power measurement of the reactor can be greatly reduced, and the measurement precision of the nuclear detectors for measuring the power of the reactor is improved.
It should also be noted that, in the case of the embodiments of the present invention, features of the embodiments and examples may be combined with each other to obtain a new embodiment without conflict.
The above description is only an embodiment of the present invention, but the scope of the present invention is not limited thereto, and the scope of the present invention is subject to the scope of the claims.
Claims (11)
1. The compensation method for the reactor power measurement is characterized in that a movable reflecting layer is arranged on the periphery of a reactor core of a reactor, the reactivity of the reactor is controlled through the displacement of the reflecting layer, and a plurality of nuclear detectors are arranged outside the reflecting layer; the compensation method is used for compensating the deviation of the displacement of the reflecting layer to the power measurement value of the reactor and comprises the following steps:
obtaining power measurement values of a working group detector and a compensation group detector in the plurality of nuclear detectors;
determining the position of the reflecting layer according to the ratio of the power measurement values of the working group detector and the compensation group detector;
determining a power compensation coefficient of the working group detector according to the position of the reflecting layer;
and compensating the power measurement value of the working group detector by using the power compensation coefficient to obtain the current power value of the reactor.
2. The compensation method of claim 1, further comprising:
obtaining a function G (x) of the neutron fluence rate at each nuclear detector position along with the position change relation of the reflecting layer when the reactor power is constant;
determining a reflecting layer position relation function f1 and a compensation coefficient relation function f2 according to functions G (x) at the positions of the working group detector and the compensation group detector;
wherein the content of the first and second substances,
the function f1 is a numerical relational expression between the ratio of the neutron fluence rates at the positions of the working group detector and the compensation group detector and the position of the reflecting layer;
the function f2 is a numerical relationship between the position of the reflective layer and the power compensation coefficient of the active set detector.
3. A compensation method according to claim 2, wherein the function f1 is an inverse function of the ratio of the G (x) function of the detector of the active set to the G (x) function of the detector of the compensation set.
4. The compensation method of claim 2, wherein the function f2 is a ratio of a neutron fluence rate at a position of the workgroup detector when the reflection layer is at the reference point to a G (x) function of the workgroup detector.
5. The compensation method of any one of claims 2-4, wherein determining the power compensation factor for the active set detector based on a ratio between power measurements for the active set detector and the compensation set detector comprises:
determining the current position of the reflecting layer according to the ratio of the power measurement values of the working group detector and the compensation group detector and the function f 1;
and determining the power compensation coefficient of the working group detector according to the position of the reflecting layer and the function f2.
6. A compensation method according to any of claims 1-4, wherein the ratio between the power measurements of the active set detectors and the compensation set detectors is:
dividing the workgroup detector power measurement by the compensation group detector power measurement; or
Dividing the compensated group detector power measurement by the active group detector power measurement; or
And the difference value of the logarithmic operation is carried out on the power measured value of the working group detector and the power measured value of the compensation group detector.
7. The compensation method of claim 1, further comprising:
the positions of the active set detectors and the compensation set detectors are selected.
8. The compensation method of claim 7, wherein the selecting the positions of the active set of detectors and the compensation set of detectors comprises:
selecting the positions of the working group detector and the compensation group detector according to a function G (x) of the neutron fluence rate at each nuclear detector position along with the position change relation of the reflecting layer when the reactor power is constant;
wherein the content of the first and second substances,
when the reactor power is constant, the function value variation range of G (x) at the position of the working group detector is smaller than that of G (x) at the position of the compensation group detector, and the function value variation range is the difference value between the maximum function value and the minimum function value;
g (x) at the compensation group detector locations is a single valued function and the ratio of G (x) at the compensation group detector locations to G (x) at the working group detector locations is also a single valued function.
9. The compensation method of claim 8, wherein selecting the position of the workgroup detector further comprises:
when a plurality of reflecting layers are arranged on the periphery of the reactor core of the reactor, the position of a working group detector is selected according to the influence relationship of each reflecting layer on the neutron fluence rate at the position of each nuclear detector;
wherein, the influence relation of each reflecting layer on the neutron fluence rate at the position of the working group detector is consistent.
10. The compensation method of claim 8, wherein selecting the position of the compensation group detector further comprises:
when a plurality of reflecting layers are arranged on the periphery of the reactor core of the reactor, the position of a compensation group detector is selected according to the influence relation of each reflecting layer on the neutron fluence rate at the position of each nuclear detector;
and influence relations of the reflecting layers on neutron fluence rates at the positions of the compensation group detectors are consistent.
11. The compensation method of any one of claims 8-10, further comprising: the position of the compensation group detectors and/or the working group detectors is selected based on the spatial position in the reactor.
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